| | https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16380_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-16380.pdf | 19 | Idaho National Laboratory | Nuclear Science User Facilities | Joint R&D with NSUF Access | $500,000.00 | This project will test and characterize distributed temperature measurements in sapphire optical fiber for high-temperature radiation environments. | |
| | https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16895_TechnicalAbstract_2019CFATechnicalAbstract16895.pdf | 19 | University of Michigan | Nuclear Science User Facilities | Joint R&D with NSUF Access | $500,000.00 | This project will investigate the effect of radiation damage in optical materials on the operation and performance of laser spectroscopic sensors. Significantly beyond the scope of prior studies, this project will seek to understand the effect of simultaneous radiation damage and annealing on optical materials operated in high-temperature environments, and further evaluate the effect of irradiation on nonlinear optical absorption. | |
| | https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16297_TechnicalAbstract_2019CFATechnicalAbstract19-16297.pdf | 19 | Purdue University | Nuclear Science User Facilities | Joint R&D with NSUF Access | $500,000.00 | The objective of this project is to assess the integrity of electron beam (EB) welded powder metallurgy with hot isostatic pressing pressure vessel steel under irradiation. This project will conduct neutron irradiations and post irradiation examination (PIE) on EB. The project will systematically study the effects of composition, heat treatment, and processing on irradiation response. PIE will include microstructure, mechanical, and fracture toughness testing. | |
| | https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16567_TechnicalAbstract_2019CFATechnicalAbstract19-16567.pdf | 19 | Westinghouse Electric Company | Nuclear Science User Facilities | NSUF Access Only | $- | This project will use material from commercial pressurized water reactor baffle-former bolts (neutron irradiated Type 347 steel), available from previous failure investigations and industry research, to conduct irradiation-assisted stress corrosion cracking initiation tests under controlled experimental conditions. The research will assess the dependence of this cracking phenomena on radiation damage and reactor water chemistry (potassium hydroxide versus lithium hydroxide). | |
| | https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-16547_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-16547.pdf | 19 | Nuscale Power, LLC | Nuclear Science User Facilities | NSUF Access Only | $- | NuScale is evaluating the application of First-of-A-Kind materials for the NuScale Power Module™ that have the potential to dramatically reduce manufacturing cost and production timelines. Specifically, the objective is to obtain irradiation embrittlement testing data of base metal, weld metal, and heat-affected zone from SA-508 Grade 3 Class 2 weldments and Code Case N-774 Grade F6NM weldments. Irradiation of materials will be followed by Tension, Charpy, and Fracture Mechanics testing. | |
| | https://neup.inl.gov/FY%202019%20Abstracts1/CFA-19-17159_TechnicalAbstract_2019CFATechnicalAbstractCFA-19-17159.pdf | 19 | Kairos Power LLC | Nuclear Science User Facilities | NSUF Access Only | $- | The proposed project is to conduct very high-power TRISO particle irradiations to demonstrate significant performance margin to current Advanced Gas Reactor (AGR) tests, where the AGR program irradiations can be applied to near-term operation of a Kairos Power prototype fluoride-salt-cooled high-temperature reactor (FHR). The proposed test is exploratory in nature, designed to support a long-term advanced FHR design with very high particle powers. The irradiation test will be performed at Oak Ridge National Laboratory in the High Flux Isotope Reactor using the existing miniature fuel specimen capsule. | |
| | https://neup.inl.gov/FY%202019%20Abstracts1/2019%20CFA%20Technical%20Abstract%20%2019-17109.pdf | 19 | Westinghouse Electric Co. | Nuclear Science User Facilities | NSUF Access Only | $- | Researchers will continue the development of a remotely interrogated (magnetic coupling) in-core wireless sensor embedded within a fuel rod, which is capable of measuring critical parameters such as fuel pellet center line temperature, fuel pellet elongation, fuel rod pressure and neutron flux. The sensor will wirelessly transmit them through the fuel rod cladding and coolant without compromising the structural integrity of the fuel rod. This non-intrusive system would accelerate development of advanced fuel by providing real-time data. | |
